A significant factor in the overall efficiency of the balance of plant for a future magnetic fusion energy (MFE) reactor is the thermal performance of the divertor. A significant fraction of the reactor power is delivered to the divertor as plasma impurities and fusion products are deposited on its surface. For an advanced MFE device, an average divertor heat load of 10 MW/m² is expected at steady-state operating conditions. Helium cooling of the divertors is one of the most effective ways to accommodate such a heat load. Several helium-cooled divertor designs have been proposed and/or studied during the past decade including the T-Tube divertor, the helium-cooled flat plate (HCFP) divertor, the helium-cooled multi-jet (HEMJ) divertor, the ...
Exhausting the thermal power from a fusion tokamak is a critical engineering challenge. The life of ...
Helium-cooled, refractory heat exchangers are now under consideration for first wall and divertor ap...
The development of the divertor for the forthcoming DEMO fusion reactor stipu-lates heat flux loads ...
The heat transfer performance of the Helium-cooled Multi-jet (HEMJ) divertor was investigated. The H...
The divertor is a key plasma-facing component of future commercial magnetic fusion energy (MFE) reac...
Divertors are in-vessel, plasma-facing, components in magnetic-confinement fusion reactors. Their m...
This report represents a summary of our knowledge after little more than one year of development of ...
Within the framework of the EU power plant conceptual study (PPCS), helium-cooled modular divertor c...
In the frame of preparatory work for an European power plant conceptual study to be launched in 2000...
Experimental and numerical studies simulating the gas-cooled divertor plate design concept have been...
The International Thermonuclear Reactor (ITER) will have a single-null divertor with total power flo...
Within the european power plant conceptual study (PPCS) started in 2000 it is planned to integrate a...
Existing and potential design problems associated with the helium-cooled blanket assemblies of exper...
Application of a helium-cooled divertor together with the dual-coolant blanket concept is considered...
This paper describes a numerical and experimental investigation in support of the ARIES-CS divertor ...
Exhausting the thermal power from a fusion tokamak is a critical engineering challenge. The life of ...
Helium-cooled, refractory heat exchangers are now under consideration for first wall and divertor ap...
The development of the divertor for the forthcoming DEMO fusion reactor stipu-lates heat flux loads ...
The heat transfer performance of the Helium-cooled Multi-jet (HEMJ) divertor was investigated. The H...
The divertor is a key plasma-facing component of future commercial magnetic fusion energy (MFE) reac...
Divertors are in-vessel, plasma-facing, components in magnetic-confinement fusion reactors. Their m...
This report represents a summary of our knowledge after little more than one year of development of ...
Within the framework of the EU power plant conceptual study (PPCS), helium-cooled modular divertor c...
In the frame of preparatory work for an European power plant conceptual study to be launched in 2000...
Experimental and numerical studies simulating the gas-cooled divertor plate design concept have been...
The International Thermonuclear Reactor (ITER) will have a single-null divertor with total power flo...
Within the european power plant conceptual study (PPCS) started in 2000 it is planned to integrate a...
Existing and potential design problems associated with the helium-cooled blanket assemblies of exper...
Application of a helium-cooled divertor together with the dual-coolant blanket concept is considered...
This paper describes a numerical and experimental investigation in support of the ARIES-CS divertor ...
Exhausting the thermal power from a fusion tokamak is a critical engineering challenge. The life of ...
Helium-cooled, refractory heat exchangers are now under consideration for first wall and divertor ap...
The development of the divertor for the forthcoming DEMO fusion reactor stipu-lates heat flux loads ...